[Federal Register Volume 60, Number 173 (Thursday, September 7, 1995)]
[Notices]
[Pages 46633-46635]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 95-22185]
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NUCLEAR REGULATORY COMMISSION
[Docket Nos. 50-424 and 50-425]
Georgia Power Company, et al.; Vogtle Electric Generating Plant,
Units 1 and 2; Notice of Consideration of Issuance of Amendments to
Facility Operating Licenses and Opportunity for a Hearing
The U.S. Nuclear Regulatory Commission (the Commission) is
considering issuance of amendments to Facility Operating License Nos.
NPF-68 and NPF-84, issued to the Georgia Power Company, et al. (the
licensee), for operation of the Vogtle Electric Generating Plant (VEGP,
Vogtle), Units 1 and 2, located at the licensee's site in Burke County,
Georgia.
The proposed amendments, requested by the licensee in a letter
dated May 1, 1995, would represent a full conversion from the current
Technical Specifications (TS) to a set of TS based on NUREG-1431,
``Standard Technical Specifications, Westinghouse Plants,'' Revision 1,
dated April, 1995. NUREG-1431 was developed through working groups
composed of NRC staff members and industry representatives and has been
endorsed by the staff as part of an industry-wide initiative to
standardize and improve the TS. As part of this submittal, the licensee
has applied the criteria contained in the Commission's Final Policy
Statement on Technical Specification Improvements for Nuclear Power
Reactors of July 22, 1993, to the current Vogtle TS, and, using NUREG-
1431 as a basis, developed a proposed set of improved TS for Vogtle.
The criteria in the Final Policy Statement were subsequently added to
10 CFR 50.36, ``Technical Specifications,'' in a rule change which
became effective on August 18, 1995 (60 FR 36953).
The licensee has categorized the proposed changes to the existing
TS into four general groupings. These groupings are characterized as
administrative changes, relocated changes, more restrictive changes,
and less restrictive changes.
Non-technical, administrative changes were intended to incorporate
human-factors principles into the form and structure of the improved
plant TS so that they would be easier to use for plant operations
personnel. Administrative changes are editorial in nature or involve
the reorganization or reformatting of requirements without affecting
technical content or operational requirements. The proposed changes
include: (a) Providing the appropriate numbers, etc., for NUREG-1431
bracketed information (information which must be supplied on a plant-
specific basis, and which may change from plant to plant), (b)
identifying plant-specific wording for system names, etc., and (c)
changing NUREG-1431 section wording to conform to existing licensee
practices.
Relocated changes, those current TS requirements which do not
satisfy or fall within any of the four criteria specified in the
Commission's policy statement, may be relocated to appropriate
licensee-controlled documents. The licensee's application states that
such requirements will be relocated from the TS to administratively
controlled documents such as the Final Safety Evalution Report. Changes
made to these documents will be made pursuant to 10 CFR 50.59 or other
appropriate control mechanisms. These changes reduce the number of
current TS requirements but the actual commitment to continue to
perform the requirement will be unchanged upon implementation of the
improved TS.
The licensee's proposed improved TS include certain more
restrictive requirements than are contained in the current TS, which
are either more conservative than corresponding requirements in the
current TS, or are additional restrictions that are contained in NUREG-
1431 but are not contained in the current TS. Examples
[[Page 46634]]
of more restrictive requirements include: placing a limiting condition
for operation (LCO) on plant equipment that is not required by the
present TS to be operable; more restrictive requirements to restore
inoperable equipment; and more restrictive surveillance requirements.
Less restrictive changes are those where current requirements are
relaxed or eliminated, or new flexibility is provided. The more
significant ``less restrictive'' requirements are justified on a case-
by-case basis. When requirements have been shown to provide little or
no safety benefit, their removal from the TS may be appropriate. In
most cases, relaxations previously granted to individual plants on a
plant-specific basis were the result of (a) generic NRC actions, (b)
new NRC staff positions that have evolved from technological
advancements and operating experience, or (c) resolution of the Owners
Groups' comments on the improved Standard Technical Specifications.
Generic relaxations contained in NUREG-1431 were reviewed by the staff
and found to be acceptable because they are consistent with current
licensing practices and NRC regulations. The licensee's design was
reviewed to determine if the specific design basis and licensing basis
are consistent with the technical basis for the model requirements in
NUREG-1431 and thus provides a basis for these revised TS.
These administrative, relocated, more restrictive and less
restrictive changes to the requirements of the current TS do not result
in operations that will alter assumptions relative to mitigation of an
analyzed accident or transient event.
In addition to the changes described above, the licensee proposed
certain changes to the current TS that are both less restrictive and
are not within the scope of application for conversion to the guidance
of NUREG-1431. All of the differences will be reviewed by the NRC staff
and a determination will be made regarding the approval or disapproval
of each item as a part of this licensing action. Specifically, the
licensee identified the following instances where their submittal
varied from the provisions of NUREG-1431.
Shutdown margin requirements for Mode 2 with Keff <1.0 are
deleted. The applicability of the TS requirements for shutdown bank
insertion limits, the requirement to verify a nonindicating rod
position immediately after movement of more than 24 steps, and the
required actions and surveillance requirements for quadrant power tilt
ratio are revised.
With regard to reactor trip system (RTS) instrumentation, revisions
are made to: (1) Three NUREG-1431 surveillances based on Vogtle
operating practices and vendor recommendations; (2) notes 1 and 2 to
NUREG-1431 LCO 3.3.1 required actions for Condition T (one RTS channel
inoperable); (3) the NUREG-1431 surveillance requirements for the P-7
interlock; (4) the completion time for required actions with one
intermediate range neutron flux channel inoperable (LCO 3.3.1 Condition
F); and, (5) the Applicable Modes or other specified conditions for the
RTS Interlocks P-7, P-8, P-9, P-10, and P-13.
For the Engineered Safety Features Actuation System
instrumentation, the surveillance intervals for the Channel Operational
Test of the refueling water storage tank level Low-Low signal for Semi-
Automatic Switchover to Containment Emergency Sump function and the
surveillance interval for the Channel Operational Test of the low
Reactor Coolant System (RCS) Tavg function are increased from
monthly to quarterly.
For the RCS, the surveillance interval for the pressurizer heater
capacity is revised from 92 days to 18 months. Also, the completion
time for depressurizing the RCS in the event of an inoperable cold
overpressure protection system is revised from 8 hours to 12 hours, and
the requirements for performing RCS water inventory balances are
revised. The lift setpoints for the residual heat removal suction
relief valves, the RCS vent capacity for cold overpressure protection,
and the pressurizer safety valve lift settings are moved to the Bases
of the improved TS.
For the Emergency Core Cooling System, the requirements for seal
water injection flow is revised to locate the limits for seal injection
flow to the Bases. Also, the Mode 4 requirements are revised.
For containment systems, the current allowed outage time for the
containment spray and cooling systems is revised from 72 hours to 14
days, and the air lock door interlock mechanism surveillance frequency
is revised from the current frequency of 6 months to 18 months. An
allowance to open the 14-inch purge valves for maintenance testing is
added.
For other plant systems, the Condensate Storage Tank LCO is revised
consistent with a planned design modification that will result in two
100% capacity tanks. The surveillance requirement to operate the Piping
Penetration Area Filtration and Exhaust System (PPAFES) monthly for
10 continuous hours is revised to operate for 15
minutes and the heater capacity verification is deleted. The Completion
Time to reduce the Power Range Neutron Flux High Trip setpoints is
increased from 4 hours to 12 hours. The currently licensed footnote in
the Control Room Emergency Filtration System (CREFS) LCO that requires
Train B CREFS to be started whenever a CREFS train must be placed in
service to comply with Actions is deleted. A Note is added to the
current LCO for the engineered safety feature room coolers and the
safety-related chiller system providing an exception to the LCO for
surveillance testing.
For electrical systems, several revisions to the LCO for AC
Sources--Operating were proposed to support the addition of a new
Standby Auxiliary Transformer as a Unit 1 and Unit 2 common offsite
circuit. Also, the diesel generator accelerated test frequency
requirements in the AC Sources--Operating LCO are relocated outside of
the TS.
Regarding administrative controls, the Ventilation Filter Testing
Program is revised consistent with the proposed change in the Plant
Systems Chapter for the deletion of the heater capacity test for the
PPAFES. The reference to the ASTM standard in Paragraph 5.5.13.c is
deleted.
Before issuance of the proposed license amendments, the Commission
will have made findings required by the Atomic Energy Act of 1954, as
amended (the Act) and the Commission's regulations.
By October 10, 1995, the licensee may file a request for a hearing
with respect to issuance of the amendments to the subject facility
operating licenses and any person whose interest may be affected by
this proceeding and who wishes to participate as a party in the
proceeding must file a written request for a hearing and a petition for
leave to intervene. Requests for a hearing and a petition for leave to
intervene shall be filed in accordance with the Commission's ``Rules of
Practice for Domestic Licensing Proceedings'' in 10 CFR Part 2.
Interested persons should consult a current copy of 10 CFR 2.714 which
is available at the Commission's Public Document Room, the Gelman
Building, 2120 L Street, NW., Washington, DC, and at the local public
document room located at the Burke County Library, 412 Fourth Street,
Waynesboro, Georgia. If a request for a hearing or petition for leave
to intervene is filed by the above date, the Commission or an Atomic
Safety and Licensing Board, designated by the Commission or by the
Chairman of the Atomic Safety and Licensing Board
[[Page 46635]]
Panel, will rule on the request and/or petition; and the Secretary or
the designated Atomic Safety and Licensing Board will issue a notice of
hearing or an appropriate order.
As required by 10 CFR 2.714, a petition for leave to intervene
shall set forth with particularity the interest of the petitioner in
the proceeding, and how that interest may be affected by the results of
the proceeding. The petition should specifically explain the reasons
why intervention should be permitted with particular reference to the
following factors: (1) The nature of the petitioner's right under the
Act to be made a party to the proceeding; (2) the nature and extent of
the petitioner's property, financial, or other interest in the
proceeding; and (3) the possible effect of any order which may be
entered in the proceeding on the petitioner's interest. The petition
should also identify the specific aspect(s) of the subject matter of
the proceeding as to which petitioner wishes to intervene. Any person
who has filed a petition for leave to intervene or who has been
admitted as a party may amend the petition without requesting leave of
the Board up to 15 days prior to the first prehearing conference
scheduled in the proceeding, but such an amended petition must satisfy
the specificity requirements described above.
Not later than 15 days prior to the first prehearing conference
scheduled in the proceeding, a petitioner shall file a supplement to
the petition to intervene which must include a list of the contentions
which are sought to be litigated in the matter. Each contention must
consist of a specific statement of the issue of law or fact to be
raised or controverted. In addition, the petitioner shall provide a
brief explanation of the bases of the contention and a concise
statement of the alleged facts or expert opinion which support the
contention and on which the petitioner intends to rely in proving the
contention at the hearing. The petitioner must also provide references
to those specific sources and documents of which the petitioner is
aware and on which the petitioner intends to rely to establish those
facts or expert opinion. Petitioner must provide sufficient information
to show that a genuine dispute exists with the applicant on a material
issue of law or fact. Contentions shall be limited to matters within
the scope of the amendment under consideration. The contention must be
one which, if proven, would entitle the petitioner to relief. A
petitioner who fails to file such a supplement which satisfies these
requirements with respect to at least one contention will not be
permitted to participate as a party.
Those permitted to intervene become parties to the proceeding,
subject to any limitations in the order granting leave to intervene,
and have the opportunity to participate fully in the conduct of the
hearing, including the opportunity to present evidence and cross-
examine witnesses.
A request for a hearing or a petition for leave to intervene must
be filed with the Secretary of the Commission, U.S. Nuclear Regulatory
Commission, Washington, DC 20555, Attention: Docketing and Services
Branch, or may be delivered to the Commission's Public Document Room,
the Gelman Building, 2120 L Street, NW., Washington, DC, by the above
date. Where petitions are filed during the last 10 days of the notice
period, it is requested that the petitioner promptly so inform the
Commission by a toll-free telephone call to Western Union at 1-(800)
248-5100 (in Missouri 1-(800) 342-6700). The Western Union operator
should be given Datagram Identification Number N1023 and the following
message addressed to Herbert N. Berkow, Director, Project Directorate
II-2: petitioner's name and telephone number; date petition was mailed;
plant name; and publication date and page number of this Federal
Register notice. A copy of the petition should also be sent to the
Office of the General Counsel, U.S. Nuclear Regulatory Commission,
Washington, DC 20555, and to Ernest L. Blake, Jr., Esquire, Shaw,
Pittman, Potts, and Trowbridge, 2300 N Street, NW., Washington, DC
20037, attorney for the licensee.
Nontimely filings of petitions for leave to intervene, amended
petitions, supplemental petitions and/or requests for hearing will not
be entertained absent a determination by the Commission, the presiding
officer or the presiding Atomic Safety and Licensing Board that the
petition and/or request should be granted based upon a balancing of the
factors specified in 10 CFR 2.714(a)(1) (i)-(v) and 2.714(d).
If a request for a hearing is received, the Commission's staff may
issue the amendments after it completes its technical review and prior
to the completion of any required hearing if it publishes a further
notice for public comment of its proposed finding of no significant
hazards consideration in accordance with 10 CFR 50.91 and 50.92.
For further details with respect to this action, see the
application for amendments dated May 1, 1995, which is available for
public inspection at the Commission's Public Document Room, the Gelman
Building, 2120 L Street, NW., Washington, DC, and at the local public
document room located at the Burke County Library, 412 Fourth Street,
Waynesboro, Georgia.
Dated at Rockville, Maryland, this 31st day of August 1995.
For the Nuclear Regulatory Commission.
L. A. Wiens,
Acting Director, Project Directorate II-2, Division of Reactor
Projects--I/II, Office of Nuclear Reactor Regulation.
[FR Doc. 95-22185 Filed 9-6-95; 8:45 am]
BILLING CODE 7590-01-P